Properties of U sub 3 O sub 8 -aluminum cermet fuel

Technical Report · Sun Oct 01 00:00:00 EDT 1989

DOI:https://doi.org/10.2172/7262763· OSTI ID:7262763

Peacock, H B

Nuclear fuel elements containing U{sub 3}O{sub 8} dispersed in an aluminum matrix have been used in research and test reactors for about 30 years. These elements, sometimes called cermet fuel, are made by powder metallurgical methods (PM) and can accommodate up to approximately 50 wt % uranium in the core section of extruded tubes. Cermet fuel elements have been fabricated and irradiated at the Savannah River Site (SRS). Irradiation behavior is excellent. Extruded tubes with up to 50 wt % uranium have been successfully irradiated to fission densities of about 2 {times} 10{sup 21} fissions per cc of core. Physical, mechanical, and chemical properties of cermet fuels are assembled into a reference document. Results will be used by Argonne National Laboratory to design cermet fuel elements for possible use in the New Production Reactor at SRS. 57 refs., 33 figs., 12 tabs.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 7262763
• Report Number(s): WSRC-RP-89-981; ON: DE90008128
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
CERMETS
MECHANICAL PROPERTIES
URANIUM OXIDES U3O8
PHYSICAL PROPERTIES
ALUMINIUM
CHEMICAL COMPOSITION
CHEMICAL PROPERTIES
DENSITY
FISSION PRODUCT RELEASE
IRRADIATION
MICROSTRUCTURE
NUCLEAR FUELS
PHYSICAL RADIATION EFFECTS
SAVANNAH RIVER PLANT
SWELLING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPOSITE MATERIALS
CRYSTAL STRUCTURE
ELEMENTS
ENERGY SOURCES
FUELS
MATERIALS
METALS
NATIONAL ORGANIZATIONS
OXIDES
OXYGEN COMPOUNDS
RADIATION EFFECTS
REACTOR MATERIALS
URANIUM COMPOUNDS
URANIUM OXIDES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
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